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Filtering medium for removing radioactive strontium in drinking water, filter element and preparation method

A filter medium and radioactive strontium technology, which is applied in the field of filter medium, filter element and preparation for removing radioactive strontium in drinking water, can solve the problems of high energy consumption, secondary pollution, troublesome use of evaporation and concentration, and achieve removal rate High, harm-free, simple method effect

Inactive Publication Date: 2016-04-20
佛山市农业总公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The conventional water treatment process of the waterworks has no obvious effect on the removal of radioactive strontium; the chemical precipitation method, ion exchange method, and evaporation concentration method are troublesome to use; the RO membrane removal effect is good, but the energy consumption is large, the waste water is expensive, the cost is high, and the discharge The concentrated solution is not easy to handle, and it is easy to cause secondary pollution

Method used

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  • Filtering medium for removing radioactive strontium in drinking water, filter element and preparation method

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preparation example Construction

[0020] The invention provides a method for preparing a filter medium for removing radioactive strontium in drinking water, comprising the following steps:

[0021] a) mixing ultra-high molecular weight polyethylene powder, activated carbon powder, attapulgite powder, zeolite powder and a pore-forming agent to obtain a mixture, the ultra-high molecular weight polyethylene powder, activated carbon powder, attapulgite powder, zeolite powder and a pore-forming agent The weight ratio is 100~300:50~100:100~200:100~200:50~100;

[0022] b) pressing, sintering and cooling the mixture obtained in step a) in a mould;

[0023] The pressing pressure is 0.4MPa-1Mpa; the sintering temperature is 200°C-245°C; the sintering time is 90-120min; the cooling temperature is 40°C-60°C.

[0024] The present invention first mixes ultra-high molecular weight polyethylene powder, activated carbon powder, attapulgite powder, zeolite powder and a pore-forming agent to obtain a mixture. The ultra-high mol...

Embodiment 1

[0060] (1) Take by weighing 100 μm ultra-high molecular weight polyethylene powder 100 g in particle size, the ultra-high molecular weight polyethylene is the M-I type product of Beijing Dongfang Petrochemical Co., Ltd. Auxiliary No. 2 Factory, and its molecular weight is 1.5 million;

[0061] (2) Weighing 50g of medical activated carbon powder with a particle diameter of 100 μm, the specific surface area of ​​the medical activated carbon is 800m 2 / g;

[0062] (3) taking by weighing the zeolite powder 100g of 80 μm particle diameter according to HCl and NaCl mixed modification of the present invention;

[0063] (4) taking by weighing the attapulgite powder 100g that acidifies according to the acidification mode of the present invention with a particle diameter of 85 μm;

[0064] (5) Take 50g of pore forming agent;

[0065] (6) Put the above five kinds of powders into a mechanical stirrer and stir for 10 minutes to mix evenly;

[0066] (7) Fill the mixed powder into a tubul...

Embodiment 2

[0069] (1) Take by weighing 200 g of ultra-high molecular weight polyethylene powder with a particle size of 102 μm. The ultra-high molecular weight polyethylene is the M-III product of Beijing Dongfang Petrochemical Co., Ltd. Auxiliary No. 2 Factory, and its molecular weight is 3.5 million;

[0070] (2) Weighing 75g of medical activated carbon powder with a particle diameter of 100 μm, the specific surface area of ​​the medical activated carbon is 1500m 2 / g;

[0071](3) taking by weighing the zeolite powder 150g of 82 μm particle diameter according to HCl and NaCl mixed modification of the present invention;

[0072] (4) taking by weighing the attapulgite powder 150g that acidifies according to the acidification mode of the present invention with a particle diameter of 75 μm;

[0073] (5) Take 75g of pore forming agent;

[0074] (6) Put the above five kinds of powders into a mechanical stirrer and stir for 10 minutes to mix evenly;

[0075] (7) Fill the mixed powder into ...

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Abstract

The invention provides a preparation method of a filtering medium for removing radioactive strontium in drinking water. The preparation method comprises steps as follows: a), UHMWPE (ultra-high molecular weight polyethylene) powder, activated carbon powder, attapulgite powder, zeolite powder and a pore forming agent are mixed in the weight ratio being (100-300):(50-100):(100-200):(100-200):(50-100), and a mixture is obtained; b), the mixture obtained in the step a) is pressed, sintered and cooled in a die, wherein the pressing pressure is 0.4 MPa-1MPa, the sintering temperature ranges from 200 DEG C to 245 DEG C, the sintering time lasts for 90-120 min, and the cooling temperature ranges from 40 DEG C to 60 DEG C. The filtering medium prepared at a specific sintering temperature and cooling temperature under specific pressure has a high removal rate for radioactive strontium under the synthetic function of the raw materials, the method is simple, the filtering medium is suitable for the drinking water polluted by radioactive strontium, eliminates harm of radioactive strontium to a human body, is simple and convenient to use and low in cost, and a detection result shows that with the adoption of the filtering medium, the removal rate of radioactive strontium in the drinking water is higher than 98.8%.

Description

technical field [0001] The invention relates to a filter medium for removing radioactive strontium in drinking water and a preparation method thereof, a filter element, a water purification device and a water dispenser composed of the filter medium. Background technique [0002] With the continuous development of nuclear power applications, the disposal of radioactive nuclear waste has become an urgent problem to be solved, and it has also become a key issue for the healthy development of nuclear power. [0003] Radioactive strontium (strontium 89 and strontium 90) is produced by 235 U and 239 Produced by Pu nuclear fission, it is commonly found in radioactive water bodies. In 2011, the Fukushima nuclear power plant in Japan exploded, resulting in radioactive leakage and a large amount of waste water containing radioactive strontium was discharged. because 90 The radioactive half-life of Sr is about 30 years. It has strong biological toxicity and is difficult to discharg...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B01J20/30B01J20/26C02F1/28C02F1/00
CPCB01J20/261B01J20/12B01J20/165B01J20/28064B01J20/28066B01J20/324B01J2220/4806B01J2220/4812C02F1/003C02F1/288C02F2101/006C02F2305/04
Inventor 栾云堂周小刚田可谷景欣
Owner 佛山市农业总公司
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